ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Four million nuclear jobs by 2050: Who will do them?
Industry leaders from around the globe met this month to discuss the talent development that will be necessary for the long-term success of the nuclear industry.
The International Conference on Nuclear Knowledge Management and Human Resources Development, hosted by the International Atomic Energy Agency, was held in Vienna earlier this month. Discussed there was the agency’s forecast for nuclear capacity to more than double—or hopefully triple—by 2050 and the requirement of more than four million professionals to support the industry.
Todd K. Campbell, Edgar Robert Gilbert, Cheryl Knox Thornhill, Bernard J. Wrona
Nuclear Technology | Volume 84 | Number 2 | February 1989 | Pages 182-195
Technical Paper | Fuel Cycle | doi.org/10.13182/NT89-A34186
Articles are hosted by Taylor and Francis Online.
To support dry storage technology, oxidation tests were conducted with light water reactor spent fuel. The initial rate of weight gain for spent fuel was up to 50 times greater than the initial rate for nonirradiated pellets. Spent fuel formed measurable U4O9+x particulates at weight gains significantly higher than those at which the nonirradiated pellets formed U3O8 powder. Initial test results on three types of pressurized water reactor (PWR) spent fuel indicated that fuel type had a significant influence on weight gain. Additional tests were performed at temperature levels from 135 to 230°C on fuel with burnups from 8 to 34 GWd/ tonne U irradiated in five different reactors. The tests were conducted in static air at controlled moisture levels in a 105 R/h gamma field. In the 230°C tests, weight gains for PWR and boiling water reactor (BWR) fuels exceeded 4 wt% after 4000 h of exposure. Powder formation time on BWR fuels increased with increasing burnup; weight gain magnitudes were independent of fuel burnup.